Zirconium was treated with different doses (10–400 kGy) of radiation; leading to the surface oxide formation. High doses of radiation (D ≥ 120 kGy) led formation of a stable protective surface oxide phase with low water splitting ability. However, higher doses (D ≥ 400 kGy) led to catastrophic oxidation of zirconium. In the thermal process, the values of G (H2) and W(H2) for ZrO2 were 1.18 molecules/100 eV and 2.24 molecules/g. These values for ZrZrO2 were 2.22 molecules/100 eV and 2.36 molecules/g. In the radiation-thermal process, the values of G (H2) and W(H2) for ZrO2 were 2.30 molecules/100 eV and 4.42 molecules/g. These values for ZrZrO2 were 5.58 molecules/100 eV and 4.95 molecules/g. It was observed that hydrogen production was greater in the radiation-thermal process than in the thermal process only. Similarly, the hydrogen production was greater with ZrZrO2 in comparison to ZrO2. The present research is useful in nuclear reactors with zirconium having oxide layers and as a future hydrogen production method by water splitting.

中文翻译：

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水分解制氢过程中锆表面的辐射催化活性


用不同剂量（10-400 kGy）的辐射处理锆；导致表面氧化物的形成。高剂量辐射（D ≥ 120 kGy）导致形成稳定的保护性表面氧化物相，其水分解能力较低。然而，较高剂量（D ≥ 400 kGy）会导致锆的灾难性氧化。在热处理过程中，ZrO2的G(H2)和W(H2)值为1.18分子/100eV和2.24分子/g。 ZrZrO2 的这些值为 2.22 分子/100 eV 和 2.36 分子/g。在辐射热过程中，ZrO2的G(H2)和W(H2)值为2.30分子/100eV和4.42分子/g。 ZrZrO2 的这些值为 5.58 分子/100 eV 和 4.95 分子/g。据观察，辐射热过程中的氢产量比仅热过程中的氢产量更高。同样，与 ZrO2 相比，ZrZrO2 的氢气产量更高。目前的研究可用于具有氧化层的锆核反应堆，并可作为未来通过水分解制氢的方法。